Nuclear fuel element having oxidation resistant cladding

Details Nuclear fuel element having oxidation resistant cladding Nuclear fuel element having oxidation resistant cladding

G - Physics

21

C

359/66, 359/82,

G21C 3/20 (2006.01) C22C 16/00 (2006.01) G21C 3/06 (2006.01)

Patent

CA 1319450

24NT 04920 NUCLEAR FUEL ELEMENT HAVING OXIDATION RESISTANT CLADDING ABSTRACT OF THE DISCLOSURE Nuclear fuel elements for use in the core of a nuclear reactor include an improved composite cladding having a zirconium barrier layer metallurgically bonded on the inside surface of a zirconium alloy tube, wherein the inside surface of the barrier is alloyed with preselected elemental impurities to improve oxidation resistance. The zirconium barrier layer forms a shield between the zirconium alloy tube and a core of nuclear fuel material enclosed in the composite cladding. The alloy layer formed on the barrier surface acts to inhibit cracking during the tube production fabrication step and limits oxidation in the event that the cladding is breached during operation of the reactor, allowing the entrance of water or steam into the fuel element.

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